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ADAPTATION OF CRACK GROWTH DETECTION TECHNIQUES TO U.S. MATERIAL TEST REACTORS

机译:将裂缝生长检测技术适应美国材料测试反应器

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Idaho National Laboratory and the Massachusetts Institute of Technology Nuclear Reactor Laboratory researchers have recently completed a project to develop a test rig capable of evaluating the potential for irradiation-assisted stress corrosion cracking in the high-flux conditions possible in U.S. material test reactors. Adapting techniques pioneered at the Halden Boiling Water Reactor, the project included designing and testing the loader mechanism, testing individual test rig components and electronics support equipment, and autoclave testing of the rig design. Technical challenges involved developing robust connections to the specimen for the applied current and voltage measurements, selecting appropriate ceramic insulating materials that can endure light-water reactor environments, coping with the high electromagnetic noise environment of a reactor core at full power, and accommodating material property changes in the specimen, primarily associated with fast-neutron damage that changes specimen resistance without additional crack growth. The project culminated with an in-pile demonstration at the Massachusetts Institute of Technology Research Reactor. The test rig and associated support equipment were used to apply loads to a representative compact tensile specimen and measure crack growth using the direct current potential drop method. Although the test period was limited to approximately 70 days and the accumulated neutron dose was relatively small, successful operation of the test rig was demonstrated. The specimen was cycled more than 8,000 times (more than typical for a long-term irradiation-assisted stress corrosion cracking test), which was sufficient to propagate a crack of over 2 mm. Post-irradiation measurements of the specimen confirmed a crack length equivalent to that inferred by the direct current potential drop signals. Measurements also demonstrated the necessary infrastructure for handling the irradiated sample rig and satisfactory performance of a low-cost system for crack measurement in the hot cell.
机译:爱达荷国家实验室和马萨诸塞州的技术学院核反应堆实验室研究人员最近完成了一个项目,开发了一种试验室,能够评估在美国材料测试反应器中可以在可能的高通量条件下进行辐射辅助应力腐蚀裂纹的可能性。适应技术在Halden沸水反应器中开创,该项目包括设计和测试装载机机构,测试各个试验台部件和电子支持设备,以及钻机设计的高压灭菌器测试。技术挑战涉及开发与施加电流和电压测量标本的稳健连接,选择适当的陶瓷绝缘材料,可以忍受光 - 水反应器环境,以全功率为电料核心的高电磁噪声环境,以及适应材料性能样品的变化主要与快节中子损伤相关,改变样品抗性而无需额外的裂缝生长。该项目在马萨诸塞州理工学院研究院的堆积榜上有效。测试钻机和相关的支撑设备用于将负载施加到代表性的紧凑型拉伸试样并使用直流电位下降法测量裂纹生长。虽然测试期限为约70天,但累积的中子剂量相对较小,证明了试验台的成功操作。试样循环超过8,000次(长期照射辅助应力腐蚀裂解试验的典型),其足以传播超过2mm的裂缝。标本的后照射测量确认了与直流电位液滴信号推断出的裂缝长度。测量还证明了处理辐照样品钻机的必要基础设施,以及在热电池中裂纹测量的低成本系统的令人满意的性能。

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